IR 05000289/1978024
| ML19224A556 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/04/1979 |
| From: | Caphton D, Foley T, Higgins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19224A552 | List: |
| References | |
| TASK-TF, TASK-TMR 50-289-78-24, 50-320-78-37, NUDOCS 7903080152 | |
| Download: ML19224A556 (8) | |
Text
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U.S. tiUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I 50-289/78-24 Report No.
go_qpo/7p_17 50-289 Docket No.
go_190 CPR-50 License No.. ppR-73 Priority
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Category C
Licensee:
Metropolitan Edison Company P. O. Box 542 Reading, Pennsylvania 19640 Facility Name:
Three Mile Island Nuclear Station, Units 1 and 2 Inspection at:
Middletown, Pennsylvania Inspection conducted:
December 12-14, 1978 Inspectors:
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k J. C. Higgins, Reactor Inspector date signed yp date signed
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Approved by:
D. L. Capnton, Lnlet, Nuclear 5upport date signed Section No. 1, R0&NS Branch Inspection Sum. mary:
Insoection on December 12-14, 1978 (Combined Report Nos. 50-320/78-37 and 50-289/78-24)
Areas Inspected:
Routine, unannounced inspection by regional based inspectors of hydraulic snubber surveillance (Unit 2), Inservice Testing of Pumps and Valves and licensee action on previous inspection findings (Unit 1).
The inspection involved 48 inspector-hours (Unit 1 - 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />, Unit 2 - 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />)
onsite by two NRC regional based inspectors.
Results:
Of tne three areas inspected no items of noncompliance were found in two areas and one item of noncompliance was found in the third area (Infraction - failure to implement surveillance procedure, Paragraph 4.f and 4.g).
7903080157_
Region I Form 12-3 (19 (Rev. April 77)
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DETAILS 1.
Persons Contacted The technical and supervisor level personnel listed below were contacted.
- R. Barley, Lead Mechanical Engineer, Unit 1 J. Bashista, ISI Engineer, Units 1 and 2 D. Jenkins, Mechanical Engineer, Unit 2 J. Pearce, Mechanical Engineer, Unit 1
- W.
Pream, ISI Coordinator, Units 1 and 2
- M. Rous, Superintendent of Operations, Unit 1 M. Shatto, PORC Secretary, Unit 1 H. Shipman, Operations Engineer, Unit 1
- R. Warren, Lead Mechanical Engineer, Unit 2 H. Wilson, I&C Foreman, Unit 1 The inspector also interviewed several other licensee personnel during the course of this inspection including reactor operators, engineering personnel and I&C technicians.
- denotes those present at the exit interview.
2.
Licensee Action on Previous laspection Findinos (0 pen) Unresolved item (289/78-01-01): The inspector reviewed sur-veillance procedure 1301-9.9, Hydraulic Shock and Sway Suppressors, Revision 9, dated October 6, 1978.
The licensee has regrouped precedure data sheets to facilitate proper documentation.
All shock suppressors covered by the Technical Specifications are included in the data sheets. A change to Administrative Procedure [A/P) 1010, however, has not been completed at this time.
This item remains open pending review of A/P 1010, which will change the requirements for ccmpleting E&D sheets.
(Closed) Unresolved item (289/78-01-03): The licensee has submitted Technical Specification Change Regilest #85 dated December 4, 1978 to the NRC.
This change request adds safety-related snubber BS-26A and deletes other nonsafety related snubbers from the licensee's technical specifications.
CF-4 was determ ned to be a spring hanger and as such i
was not added to the list of safety related snubbers.
This item is resolved.
(0 pen) Unresolved item (289/78-01-04): The inspector reviewed Surveil-lance Procedure (SP) 1300-IV25, " Inservice Inspection of Piping Supports and Hangers not welded to a Pressure Boundary" and determined that the licensee has not yet incorporated a verification of snubber settings
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as required by Section XI of the ASME Code.
The licensee representa-tive stated that they would incorporate appropriate measurements and acceptance criteria into the procedure to ensure that the snubber is not at either end of its operating range and has room for thermal g rowth.
This item remains open pending revisiori of SP 1300-IV25.
(0 pen) Unresolved item (289/77-09-02):
a.
The inspector reviewed Surveillance Procedure 1301-9.9 " Hydraulic Shock and Sway Suppressors Visual Inspection," Revision 9, dated October 6, 1978.
The inspector noted that the licensee has not incorporated a satisfactory verification of snubber piston settings that would ensure allowance for thermal growth without hitting the mechanical stops.
The licensee stated that a measure-ment verifying the snubber piston setting to allow for thermal growth without hitting the mechanical stops would be incorporated into the procedure for all snubbers except those which are con-sidered inaccessible or in high radiation areas.
The inaccessible or high radiation area snubbers would have their piston positions observed by remote visual examination in lieu of an actual measurement in an attempt to determine that the snubber is not hitting its mechanical stops.
b.
Snubber bleed holes are presently being verified to be clear during the functional testing of snubbers.
The inspector made a tour of the facility and visually noted that snubber bleed holes were clear and that the snubbers and supports appeared to be in generally good condition.
c.
Greasing of snubber clevis fittings was discussed with the licensee.
At present the licensee has no method of verifying that snubber clevis fittings will be lubricated over the lifetime of the facility.
The licensee's representative stated that a schedule vould be established and implemented for ensuring
- lubrication of these fittings prior to the canpletion of the next refueling outage.
This item remains open pending resolution of items a and c.
3.
Inservice Testina of Pumps a.
Documents Reviewed
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Unit 1 Program submittal letters from Metropolitan Edison to NRC dated August
'7, 1977 and September 30, 1977.
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Unit 2 Program submittal letters from Metropolitan Edison
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to NRC dated February 21, 1978 and January 3, 1978.
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Letters from NRC to Metropolitan Edison dated December 20, 1977, ano November 20, 1978.
ASME Boiler and Pressure Vessel Code,Section XI, Subsection
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IWP, " Inservice Testing of Pumps in Nuclear Power Plants" 1974 edition with Summer 1975 Addenda.
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Ops Dept. Memorandum 78-5 dated March 15,1978, "Use of In-service (ISI) Tags."
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AP 1041, " Unit 1 ISI Systems List and Retest Requirements."
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AP 1042, " Unit 2 ISI Systems List and Retest Requirements."
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Unit 1 Surveillance Procedure 1300-3F, " Motor Driven Emergency Feedwater Pump Functional Test."
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Unit 1 Surveillance Procedure 1300-38, " Decay Heat Removal Pumr Functional Test and Decay Heat Removal System Valve Operability Test."
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Unit 1 Surveillance Procedure 1300-3H A/B, "Makeu, Pump and Valve Functional Tests."
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Unit 2 Surveillance Procedure 2303-M27 A/B, " Motor Driven Emergency Feedpump Functional Test and Valve Operability Test."
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Unit 2 Surveillance Procedure 2303-M30 A/B, "NSCCW Pump Functional Test and Valve Operability Test."
b.
Scope The inspector reviewed the licensee's pump test procedures for conformance with Subsection IWP of Section XI (IWP) as modified by his submittals to the NRC.
The inspector verified that testing of all pumps in the program submittal was covered by properly approved procedures and that a sampling of the procedures met the requirements of IWP.
The inspector reviewed a sampling of completed test results for pump tests performed between January and November 1978.
With the exception of the below iten the inspector had no further questions in the pump testing area.
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c.
Decay Heat Removal Pumos Procedure 1300-38 for the Decay Heat Pumps does not contain an acceptability range or alert ranges for flow rate (Q) as re-quired by IWP-3100. The licensee's representative stated that their initial evaluation concluded that flow rate could not be r.aasured with available instrumentation, due to removal of an orifice in the minimum flow line.
The inspector noted that the licensee had not taken exception to this item in their program submittal to the NRC and that the system contained flow instrumentation which appeared to meet the intent of IWP-3100.
This item is unresolved.
(289/78-24-01)
4.
Inservice Testina of Valves a.
Documents Reviewed In addition to the documents listed in 3.a the inspector also reviewed the following procedures:
Unit 1 Surveillance Procedure 1300-3R, "ISI Test of MS, MU,
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RC and NS Valves During Shutdown and Inaccessible Valve Remote Indication Functional Test During Refueling."
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Unit 1 Surveillance Procedure 1300-3P, " Inservice Testing of CA, CF, RC, DH, WDL and FB Valves During Shutdown.
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Unit 1 Sur nce Procedure 1303-11.18 " Reactor Euilding Local Lear Testing."
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Unit 1 Surveillance Procedure 1303-11.3, " Main Steam Safety Valves."
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Unit 2 Surveillance Procedure 2303 P27, " Main Steam Safety Valves."
b.
Scope The inspector reviewed the licensee's valve testing procedures for conformance with Subsection IWV of Section XI (IWV) as modified by his submittals to the NRC.
On a sampling basis the inspector verified that all valves listed in the licensee's program submittal were tested by properly approved procedures.
The inspector also reviewed a sampling of completed valve test results performed between January 1978 and November 1978. With the exception of the below items, the inspector had no further questions in this area.
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c.
Main Steam Safety Relief Valves Unit 1 Surveillance Procedure 1303-11.3 for testing the Main Steam Safety Relief Valves tests 25 percent of the valves each refueling outage.
The procedure however does not contain the requirement of IWV-3510(c) for additional tests when a valve fails to function properly during a required test.
During the 1978 outage valve MS-20C failed and no additional valves were tested.
The licensee's representative stated that testing of the additional required valves was tentatively scheduled to be performed on January 8, pending availability of the vendor representative.
This i ter. is unresolved pending revision of the procedure and testing of the required valves.
(289/78-24-02)
d.
Check Valve Testing The various procedures used to verify check valve operability for normally closed checks c'o not appear to meet the requirements of IWV-3520(b)(2) for determining that the valve opens properly during the test (e.g. Unit 1, DH-V14 and 16, MU-V73A, B and C; Unit 2, MU-V143A, B and C).
This item is unresolved pending licensee review of the check valve procedures and completion of any required procedure revisions.
(289/78-24-03; 320/78-37-04)
e.
Fail-Safe Actuators The licensee's valve testing procedures do not appear to address the testing requirements of IWV 3410(e) for valves with fail-safe actuators.
This item is unresolved pending review of these valves by the licensee and incorporation of the required testing into his procedures.
(289/78-24-04; 320/78-37-05)
f.
Valve Stroke Times Unit 1 Surveillance Procedure 1300-38, 3G and 3I in step 7.4 of the acceptance criteria state that the test frequency shall be increased to monthly when valve stroke times increase by more than 25% from the previous test.
The inspector identified many valves with stroke time that increased by more than 25% and did not have their test frequency increased.
The valves identified were as follows:
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Procedure Valve No.
Stroke Time /Date Stroke Time /Date 1300-3G EF-V30A & B 14 sec/2-17-78 18 sec/5-17-78 1300-3G MS-V13B 17 sec/2-17-78 22 sec/5-17-78 1300-3I NR-VlB 150 sec/2-16-78 201 sec/4-14-78 1300-3I NR-Vic 85 sec/2-16-78 146 sec/4-14-78 1300-31 NR-V4B 158 sec/2-16-78 199 sec/4-14-78 1300-3B DH-V3 57.3 sec/3-7-78 118 sec/6-10-78 This is in noncomuliance with Technical Specification 6.8.1 which requires that written procedures be implemented.
(289/78-24-05)
g.
Quarterly Valve Test Unit 1 Surveillance Procedure 1300-3H " Makeup Pump and Valve Functional Tests," Revision 1, March 11,1978 specifies that the surveillance frequency for testing valves is 92 days.
The procedure however, was not performed from January 2,1978 to July 2,1978, a period in excess of 92 days.
This is an example of the item of noncompliance in paragraph 4.f above.
h.
Locked Valves The inspector selected a random sample of valves from the licensee's list of Section XI, Category E locked valves and per-formed an in-plant verification that these valves were locked in the recuired cosition.
Valves on the following systems were checked: Emergency Feed, Diesel Generator, Penetration Pressuri-zation and Condensate.
No discrepancies were identified.
5.
Snubber Surveillance Program a.
Procedure Review The inspector reviewed Three Mile Island Nuclear Station Unit 2 Surveillance Procedure 2305-R, " Hydraulic Snubber Inspection,"
Revision 1, dated February 6,1978 and compared this procedure with the recommendations provided in the vendor supplied main-tenance manual, " Paul Munroe Hydraulic Shock Struts," (M/M).
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The inspector noted that the procedure contained no provisions for:
(1) A verification of clear vent holes on the reservoirs, as recommended in the M/M; (2) A verification of a satisfactory hydraulic fluid level in the reservoirs as specified in the M/M; (3) A check for corrosion, paint or other material on the piston / seal area as specified in M/M; and, (4) A determination that the snuboer is not hard against the mechanical stops and has suf ficient stroke for thermal growth.
This item is unresolved.
(320/78-37-01)
b.
Snubber Maintenance A further review of the M/M revealed recommendations for various types of maintenance to be perfonned periodically on the installed snubbers.
At present the licensee nas no procedure or schedule for performing maintenance on the installed snubbers.
The licensee stated a maintenance procedure would be established by February 1, 1979.
This item is unresolved.
(320/78-37-02)
c.
Snubber Seal Material TMI Unit 2 is presently using "TEFZEL 200" seal material in the installed hydraulic snubbers.
This material has not been approved by the NRC as required by Technical Specification 4.7.8.1.
The licensee stated that they would submit to the NRC a request for approval of the "TEFZEL 200" seal material for use in TMI Unit 2 environment.
This item is unresolved pending submittal of the request.
(320/78-37-03)
6.
Unresolved Items Items about wh'ich more information is required to determine acceptability are considered unresolved.
Paragraphs 2, 3, 4, and 5 of this report con-tain unresolved items.
7.
Exit Interview At the inspection's end the inspectors held a meeting (see paragraph 1 for attendees) to discuss the inspection scope and findings.
The item of noncompliance and unresolved items were identified.
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